DOCSLIB.ORG

Spent Nuclear Fuel Assay Data for Isotopic Validation

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Spent Nuclear Fuel Assay Data for Isotopic Validation Nuclear Science NEA/NSC/WPNCS/DOC(2011)5 June 2011 www.oecd-nea.org Spent Nuclear Fuel Assay Data for Isotopic Validation State-of-the-art Report Nuclear Science NEA/NSC/WPNCS/DOC(2011)5 Spent Nuclear Fuel Assay Data for Isotopic Validation State-of-the-art Report Nuclear Science Committee Working Party on Nuclear Criticality Safety (WPNCS) Expert Group on Assay Data of Spent Nuclear Fuel (EGADSNF) © OECD 2011 NUCLEAR ENERGY AGENCY Organisation for Economic Co-operation and Development ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT The OECD is a unique forum where the governments of 34 democracies work together to address the economic, social and environmental challenges of globalisation. The OECD is also at the forefront of efforts to understand and to help governments respond to new developments and concerns, such as corporate governance, the information economy and the challenges of an ageing population. The Organisation provides a setting where governments can compare policy experiences, seek answers to common problems, identify good practice and work to co-ordinate domestic and international policies. The OECD member countries are: Australia, Austria, Belgium, Canada, Chile, the Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Israel, Italy, Japan, Luxembourg, Mexico, the Netherlands, New Zealand, Norway, Poland, Portugal, the Republic of Korea, the Slovak Republic, Slovenia, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. The European Commission takes part in the work of the OECD. OECD Publishing disseminates widely the results of the Organisation’s statistics gathering and research on economic, social and environmental issues, as well as the conventions, guidelines and standards agreed by its members. This work is published on the responsibility of the OECD Secretary-General. The opinions expressed and arguments employed herein do not necessarily reflect the official views of the Organisation or of the governments of its member countries. NUCLEAR ENERGY AGENCY The OECD Nuclear Energy Agency (NEA) was established on 1 February 1958. Current NEA membership consists of 30 OECD member countries: Australia, Austria, Belgium, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Luxembourg, Mexico, the Netherlands, Norway, Poland, Portugal, the Republic of Korea, the Slovak Republic, Slovenia, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. The European Commission also takes part in the work of the Agency. The mission of the NEA is: – to assist its member countries in maintaining and further developing, through international co-operation, the scientific, technological and legal bases required for a safe, environmentally friendly and economical use of nuclear energy for peaceful purposes, as well as – to provide authoritative assessments and to forge common understandings on key issues, as input to government decisions on nuclear energy policy and to broader OECD policy analyses in areas such as energy and sustainable development. Specific areas of competence of the NEA include the safety and regulation of nuclear activities, radioactive waste management, radiological protection, nuclear science, economic and technical analyses of the nuclear fuel cycle, nuclear law and liability, and public information. The NEA Data Bank provides nuclear data and computer program services for participating countries. In these and related tasks, the NEA works in close collaboration with the International Atomic Energy Agency in Vienna, with which it has a Co-operation Agreement, as well as with other international organisations in the nuclear field. Corrigenda to OECD publications may be found online at: www.oecd.org/publishing/corrigenda. © OECD 2011 You can copy, download or print OECD content for your own use, and you can include excerpts from OECD publications, databases and multimedia products in your own documents, presentations, blogs, websites and teaching materials, provided that suitable acknowledgment of the OECD as source and copyright owner is given. All requests for public or commercial use and translation rights should be submitted to [email protected]. Requests for permission to photocopy portions of this material for public or commercial use shall be addressed directly to the Copyright Clearance Center (CCC) at [email protected] or the Centre français d'exploitation du droit de copie (CFC) [email protected]. FOREWORD Foreword Management of nuclear fuel is a key issue for many NEA member countries with operating or decommissioned nuclear power plants. In the area of nuclear criticality safety, burn-up credit is an accepted practice for more efficient and cost effective management of irradiated fuel which takes into account a decrease in the reactivity of spent fuel due to the burn-up. In many countries burn-up credit has been implemented for spent fuel transportation, dry storage, pool storage, and in areas of spent fuel reprocessing. In many other countries the technical basis for burn-up credit is being actively developed and advanced for use in spent fuel management safety and licensing. The OECD/NEA Nuclear Science Committee (NSC) has been active in the area of criticality safety of irradiated nuclear fuel since 1980. In 1991, the OECD/NEA NSC formed the working group that in 1997 became the Working Party on Nuclear Criticality Safety (WPNCS), and the Expert Group on Burn-up Credit Criticality (EGBUC) was formed to co-ordinate burn-up credit technical activities and benchmarks of the criticality safety for irradiated nuclear fuel. Within the EGBUC, the importance of experimental assay data for irradiated nuclear fuel compositions to support validation of computer codes and nuclear data libraries used to calculate isotopic compositions used in burn-up credit has been recognised and discussed. In the EGBUC and WPNCS meetings in 2006 at Aix-en-Provence, it was decided that an effort dedicated specially to the collection and analyses of nuclear fuel assay data should be initiated, and the new Expert Group on Assay Data of Spent Nuclear Fuel (EGADSNF) was established. Because of the importance of assay data to a broad range of nuclear safety topics, the new Expert Group consists not only of members from WPNCS but also members from the standing technical Committee on the Safety of Nuclear Installations (CSNI) and the working group for the Integration Group for the Safety Case (IGSC) of the Radioactive Waste Management Committee. This report discusses the technical activities of the EGADSNF and the associated efforts of many NEA member countries to compile and document a comprehensive database of assay data to support applications related to nuclear energy and irradiated fuel safety and management. The new contributions of assay data are reviewed, with a summary of the existing database, experimental radiochemical assay measurement methods and best practices, and an uncertainty analysis. Based on the review of new assay data compiled by NEA member countries, progress to update the OECD/NEA web-based nuclear fuel nuclide composition database SFCOMPO is discussed. SPENT NUCLEAR FUEL ASSAY DATA FOR ISOTOPIC VALIDATION – © OECD 2011 3 LEADING PARTICIPANTS OF THE EXPERT GROUP ON ASSAY DATA FOR SPENT NUCLEAR FUEL Leading participants of the Expert Group on Assay Data for Spent Nuclear Fuel ALEJANO, Consuelo – Consejo de Seguridad Nuclear (Spain) BOULANGER, Daniele – ONDRAF/NIRAS (Belgium) BRADY-RAAP, Michele – Pacific Northwest National Laboratory (United States) BRENNETOT, Rene – Commissariat à l’énergie atomique (France) CHRAPCIAK, Vladimir – VUJE (Slovakia) CONDE, Jose – Consejo de Seguridad Nuclear (CSN, Spain) GAULD, Ian (Chair) – Oak Ridge National Laboratory (United States) GULLIFORD, Jim – OECD Nuclear Energy Agency GYSEMANS, Mireille – SCK•CEN (Belgium) HAVLUJ, Frantisek – Nuclear Research Institute at Rez (Czech Republic) HENNEBACH, Maik – AREVA NP GmbH (Germany) HORDOSY, Gabor – Atomic Energy Research Institute – KFKI (Hungary) ISHIGURO, Katsuhiko – Nuclear Waste Management Organization – NUMO (Japan) JUTIER, Ludyvine – IRSN (France) KILGER, Robert – GRS (Germany) KROEGER, Helge – BFS (Germany) MARKOVA, Ludmila – Nuclear Research Institute at Rez (Czech Republic) McKNIGHT, Richard – Argonne National Laboratory (United States) MICHEL-SENDIS, Franco – OECD Nuclear Energy Agency MILLS, Robert – UK National Nuclear Laboratory (United Kingdom) NEUBER, Jens Christian – AREVA NP GmbH (Germany) ORTEGO, Pedro – SEA Ingenieria y Analisis de Blindajes S. (Spain) MENNERDAHL, Dennis – E Mennerdahl Systems (Sweden) RANTA-AHO, Anssu – Teollisuuden Voima Oyj – TVO (Finland) REICHE, Ingo – BFS (Germany) RIFFARD, Cecile – Commissariat à l’énergie atomique – CEA (France) RUGAMA, Yolanda – Electricite de France – EdF (France) SANTAMARINA, Alain – Commissariat à l’énergie atomique – CEA (France) SUYAMA, Kenya (Past Chair) – Japan Atomic Energy Agency – JAEA (Japan) VAN WINCKEL, Stefaan – ITU, Karlsruhe (Germany) YAMAMOTO, Toru – Japan Nuclear Energy Safety Organization – JNES (Japan) ZWICKY, Hans-Urs – Zwicky Consulting GmbH (Switzerland) ZIMMERMAN, Colin – UK National Nuclear Laboratory (United Kingdom) 4 SPENT NUCLEAR FUEL ASSAY DATA FOR ISOTOPIC VALIDATION – © OECD 2011 TABLE OF CONTENTS Table of Contents Foreword .................................................................................................................................................. 3 List
Load more

Recommended publications
  • Spent Nuclear Fuel Pools in the US
    Spent Nuclear Fuel Pools in the U.S.: Reducing the Deadly Risks of Storage front cover WITH SUPPORT FROM: WITH SUPPORT FROM: By Robert Alvarez 1112 16th St. NW, Suite 600, Washington DC 20036 - www.ips-dc.org May 2011 About the Author Robert Alvarez, an Institute for Policy Studies senior scholar, served as a Senior Policy Advisor to the Secre- tary of Energy during the Clinton administration. Institute for Policy Studies (IPS-DC.org) is a community of public scholars and organizers linking peace, justice, and the environment in the U.S. and globally. We work with social movements to promote true democracy and challenge concentrated wealth, corporate influence, and military power. Project On Government Oversight (POGO.org) was founded in 1981 as an independent nonprofit that investigates and exposes corruption and other misconduct in order to achieve a more effective, accountable, open, and ethical federal government. Institute for Policy Studies 1112 16th St. NW, Suite 600 Washington, DC 20036 http://www.ips-dc.org © 2011 Institute for Policy Studies [email protected] For additional copies of this report, see www.ips-dc.org Table of Contents Summary ...............................................................................................................................1 Introduction ..........................................................................................................................4 Figure 1: Explosion Sequence at Reactor No. 3 ........................................................4 Figure 2: Reactor No. 3
    [Show full text]
  • Table 2.Iii.1. Fissionable Isotopes1
    FISSIONABLE ISOTOPES Charles P. Blair Last revised: 2012 “While several isotopes are theoretically fissionable, RANNSAD defines fissionable isotopes as either uranium-233 or 235; plutonium 238, 239, 240, 241, or 242, or Americium-241. See, Ackerman, Asal, Bale, Blair and Rethemeyer, Anatomizing Radiological and Nuclear Non-State Adversaries: Identifying the Adversary, p. 99-101, footnote #10, TABLE 2.III.1. FISSIONABLE ISOTOPES1 Isotope Availability Possible Fission Bare Critical Weapon-types mass2 Uranium-233 MEDIUM: DOE reportedly stores Gun-type or implosion-type 15 kg more than one metric ton of U- 233.3 Uranium-235 HIGH: As of 2007, 1700 metric Gun-type or implosion-type 50 kg tons of HEU existed globally, in both civilian and military stocks.4 Plutonium- HIGH: A separated global stock of Implosion 10 kg 238 plutonium, both civilian and military, of over 500 tons.5 Implosion 10 kg Plutonium- Produced in military and civilian 239 reactor fuels. Typically, reactor Plutonium- grade plutonium (RGP) consists Implosion 40 kg 240 of roughly 60 percent plutonium- Plutonium- 239, 25 percent plutonium-240, Implosion 10-13 kg nine percent plutonium-241, five 241 percent plutonium-242 and one Plutonium- percent plutonium-2386 (these Implosion 89 -100 kg 242 percentages are influenced by how long the fuel is irradiated in the reactor).7 1 This table is drawn, in part, from Charles P. Blair, “Jihadists and Nuclear Weapons,” in Gary A. Ackerman and Jeremy Tamsett, ed., Jihadists and Weapons of Mass Destruction: A Growing Threat (New York: Taylor and Francis, 2009), pp. 196-197. See also, David Albright N 2 “Bare critical mass” refers to the absence of an initiator or a reflector.
    [Show full text]
  • The Nuclear Waste Primer September 2016 What Is Nuclear Waste?
    The Nuclear Waste Primer September 2016 What is Nuclear Waste? Nuclear waste is the catch-all term for anything contaminated with radioactive material. Nuclear waste can be broadly divided into three categories: • Low-level waste (LLW), comprised of protective clothing, medical waste, and other lightly-contaminated items • Transuranic waste (TRU), comprised of long-lived isotopes heavier than uranium • High-level waste (HLW), comprised of spent nuclear fuel and other highly-radioactive materials Low-level waste is relatively short-lived and easy to handle. Currently, four locations for LLW disposal exist in the United States. Two of them, Energy Solutions in Clive, Utah and Waste Control Specialists in Andrews, Texas, accept waste from any U.S. state. Transuranic waste is often a byproduct of nuclear weapons production and contains long-lived radioactive elements heavier than uranium, like plutonium and americium. Currently, the U.S. stores TRU waste at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. High-level waste includes spent nuclear fuel and the most radioactive materials produced by nuclear weapons production. Yucca Mountain is the currently designated high-level waste repository for the United States. 1 | What is Spent Nuclear Fuel? Spent nuclear fuel (SNF), alternatively referred to as used nuclear fuel, is the primary byproduct of nuclear reactors. In commercial power reactors in the U.S., fuel begins as uranium oxide clad in a thin layer of zirconium-aluminum cladding. After several years inside of the reactor, around fi ve percent of the uranium has been converted in some way, ranging from short-lived and highly radioactive fi ssion products to long-lived actinides like plutonium, americium, and neptunium.
    [Show full text]
  • Nuclear Transmutation Strategies for Management of Long-Lived Fission
    PRAMANA c Indian Academy of Sciences Vol. 85, No. 3 — journal of September 2015 physics pp. 517–523 Nuclear transmutation strategies for management of long-lived fission products S KAILAS1,2,∗, M HEMALATHA2 and A SAXENA1 1Nuclear Physics Division, Bhabha Atomic Research Centre, Mumbai 400 085, India 2UM–DAE Centre for Excellence in Basic Sciences, Mumbai 400 098, India ∗Corresponding author. E-mail: [email protected] DOI: 10.1007/s12043-015-1063-z; ePublication: 27 August 2015 Abstract. Management of long-lived nuclear waste produced in a reactor is essential for long- term sustenance of nuclear energy programme. A number of strategies are being explored for the effective transmutation of long-lived nuclear waste in general, and long-lived fission products (LLFP), in particular. Some of the options available for the transmutation of LLFP are discussed. Keywords. Nuclear transmutation; long-lived fission products; (n, γ ) cross-section; EMPIRE. PACS Nos 28.41.Kw; 25.40.Fq; 24.60.Dr 1. Introduction It is recognized that for long-term energy security, nuclear energy is an inevitable option [1]. For a sustainable nuclear energy programme, the management of long-lived nuclear waste is very critical. Radioactive nuclei like Pu, minor actinides like Np, Am and Cm and long-lived fission products like 79Se, 93Zr, 99Tc, 107Pd, 126Sn, 129I and 135Cs constitute the main waste burden from a power reactor. In this paper, we shall discuss the management strategies for nuclear waste in general, and long-lived fission products, in particular. 2. Management of nuclear waste The radioactive nuclei which are produced in a power reactor and which remain in the spent fuel of the reactor form a major portion of nuclear waste.
    [Show full text]
  • 小型飛翔体／海外 ［Format 2］ Technical Catalog Category
    小型飛翔体／海外 ［Format 2］ Technical Catalog Category Airborne contamination sensor Title Depth Evaluation of Entrained Products (DEEP) Proposed by Create Technologies Ltd & Costain Group PLC １．DEEP is a sensor analysis software for analysing contamination. DEEP can distinguish between surface contamination and internal / absorbed contamination. The software measures contamination depth by analysing distortions in the gamma spectrum. The method can be applied to data gathered using any spectrometer. Because DEEP provides a means of discriminating surface contamination from other radiation sources, DEEP can be used to provide an estimate of surface contamination without physical sampling. DEEP is a real-time method which enables the user to generate a large number of rapid contamination assessments- this data is complementary to physical samples, providing a sound basis for extrapolation from point samples. It also helps identify anomalies enabling targeted sampling startegies. DEEP is compatible with small airborne spectrometer/ processor combinations, such as that proposed by the ARM-U project – please refer to the ARM-U proposal for more details of the air vehicle. Figure 1: DEEP system core components are small, light, low power and can be integrated via USB, serial or Ethernet interfaces. 小型飛翔体／海外 Figure 2: DEEP prototype software ２．Past experience (plants in Japan, overseas plant, applications in other industries, etc) Create technologies is a specialist R&D firm with a focus on imaging and sensing in the nuclear industry. Createc has developed and delivered several novel nuclear technologies, including the N-Visage gamma camera system. Costainis a leading UK construction and civil engineering firm with almost 150 years of history.
    [Show full text]
  • Integrity of Reactor Pressure Vessels in Nuclear Power Plants: Assessment of Irradiation Embrittlement Effects in Reactor Pressure Vessel Steels No
    156 pages, 9mm IAEA Nuclear Energy Series IAEA Nuclear No. No. NP-T-3.11 No. No. Steels Vessel Pressure Reactor in Effects Embrittlement Irradiation of Assessment Plants: Power Nuclear in Vessels Pressure Reactor of Integrity IAEA Nuclear Energy Series No. NP-T-3.11 Basic Integrity of Reactor Principles Pressure Vessels in Nuclear Power Plants: Objectives Assessment of Irradiation Embrittlement Guides Effects in Reactor Pressure Vessel Steels Technical Reports INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA ISBN 978–92–0–101709–3 ISSN 1995–7807 P1382_covI-IV.indd 1 2009-05-05 11:14:48 INTEGRITY OF REACTOR PRESSURE VESSELS IN NUCLEAR POWER PLANTS: ASSESSMENT OF IRRADIATION EMBRITTLEMENT EFFECTS IN REACTOR PRESSURE VESSEL STEELS The following States are Members of the International Atomic Energy Agency: AFGHANISTAN GUATEMALA OMAN ALBANIA HAITI PAKISTAN ALGERIA HOLY SEE PALAU ANGOLA HONDURAS PANAMA ARGENTINA HUNGARY PARAGUAY ARMENIA ICELAND PERU AUSTRALIA INDIA PHILIPPINES AUSTRIA INDONESIA POLAND AZERBAIJAN IRAN, ISLAMIC REPUBLIC OF PORTUGAL BANGLADESH IRAQ QATAR BELARUS IRELAND REPUBLIC OF MOLDOVA BELGIUM ISRAEL ROMANIA BELIZE ITALY RUSSIAN FEDERATION BENIN JAMAICA SAUDI ARABIA BOLIVIA JAPAN SENEGAL BOSNIA AND HERZEGOVINA JORDAN SERBIA BOTSWANA KAZAKHSTAN SEYCHELLES BRAZIL KENYA SIERRA LEONE BULGARIA KOREA, REPUBLIC OF SINGAPORE BURKINA FASO KUWAIT SLOVAKIA CAMEROON KYRGYZSTAN SLOVENIA CANADA LATVIA SOUTH AFRICA CENTRAL AFRICAN LEBANON SPAIN REPUBLIC LIBERIA SRI LANKA CHAD LIBYAN ARAB JAMAHIRIYA SUDAN CHILE LIECHTENSTEIN SWEDEN CHINA LITHUANIA
    [Show full text]
  • Annual Report JSC CONCERN ROSENERGOATOM for 2009
    Annual Report JSC CONCERN ROSENERGOATOM FOR 2009 Safety Effi ciency Responsibility Safety Effi ciency Responsibility JSC Concern Rosenergoatom Annual report for 2009 Content I. GENERAL INFORMATION 1. Preamble 7 1.1. On the Annual Report 7 2. Statements of top management of Rosenergoatom 8 2.1. Statement of the Chairman of the Board of Directors of Rosenergoatom 8 2.2. Statement of the General Director of Rosenergoatom 9 3. General information on Rosenergoatom 10 4. Key corporate events in 2009 11 5. Mission of Rosenergoatom 13 6. Management 13 6.1. Management structure 13 6.2. Management methods and corporate policy 24 II. CORE BUSINESS 7. Strategy 29 7.1. Positions of Rosenergoatom within the industry 29 7.2. Strategy of Rosenergoatom 30 7.3. Rosenergoatom’s medium-term development objectives and tasks (2009–2011) 30 7.4. Key performance indicators of Rosenergoatom 31 7.5. Key risks associated with Rosenergoatom’s operations 31 8. Rosenergoatom. Facts and fi gures 32 8.1. Generating capacities of Rosenergoatom 34 8.2. Electricity generation at Russian NPPs 44 8.3. Maintenance and repairs 45 8.4. Lifetime extension of NPP units 46 8.5. Production growth program 46 8.6. Construction of new power units 47 9. Priority areas of operations of Rosenergoatom 49 9.1. Production and marketing activities of Rosenergoatom 49 9.2. Investments 50 9.3. Innovation and competitive growth 50 III. CORPORATE RESPONSIBILITY 10. Safety 53 10.1. Safety indicators 53 10.2. Ensuring nuclear and radiation safety and non-proliferation of nuclear materials 55 4 JSC Concern Rosenergoatom 10.3.
    [Show full text]
  • Re-Examining the Role of Nuclear Fusion in a Renewables-Based Energy Mix
    Re-examining the Role of Nuclear Fusion in a Renewables-Based Energy Mix T. E. G. Nicholasa,∗, T. P. Davisb, F. Federicia, J. E. Lelandc, B. S. Patela, C. Vincentd, S. H. Warda a York Plasma Institute, Department of Physics, University of York, Heslington, York YO10 5DD, UK b Department of Materials, University of Oxford, Parks Road, Oxford, OX1 3PH c Department of Electrical Engineering and Electronics, University of Liverpool, Liverpool, L69 3GJ, UK d Centre for Advanced Instrumentation, Department of Physics, Durham University, Durham DH1 3LS, UK Abstract Fusion energy is often regarded as a long-term solution to the world's energy needs. However, even after solving the critical research challenges, engineer- ing and materials science will still impose significant constraints on the char- acteristics of a fusion power plant. Meanwhile, the global energy grid must transition to low-carbon sources by 2050 to prevent the worst effects of climate change. We review three factors affecting fusion's future trajectory: (1) the sig- nificant drop in the price of renewable energy, (2) the intermittency of renewable sources and implications for future energy grids, and (3) the recent proposition of intermediate-level nuclear waste as a product of fusion. Within the scenario assumed by our premises, we find that while there remains a clear motivation to develop fusion power plants, this motivation is likely weakened by the time they become available. We also conclude that most current fusion reactor designs do not take these factors into account and, to increase market penetration, fu- sion research should consider relaxed nuclear waste design criteria, raw material availability constraints and load-following designs with pulsed operation.
    [Show full text]
  • From Gen I to Gen III
    From Gen I to Gen III Gabriel Farkas Slovak University of Technology in Bratislava Ilkovicova 3, 81219 Bratislava [email protected] 14. 9. 2010 1 Evolution of Nuclear Reactors Generation I - demonstration reactors Generation II - working in the present Generation III - under construction 14. 9. 2010 2 Generation IV - R&D 14. 9. 2010 3 Expected development in nuclear technologies Prolongation of lifetieme of existing nuclear reactors Construction of new reactors in frame of Gen. III and IV . Figure 1 Replacement staggered over a 30-year period (2020 - 2050) Rate of construction : 2,000 MW/year 70000 60000 Lifetime 50000 prolongation 40000 Generation IV 30000 Actual reactors 20000 Generation III+ 10000 0 197519801985199019952000200520102015202020252030203520402045205020552060 14. 9. 2010 Average plant life : 48 years 4 Nuclear in Europe (Nuclear ~ 32% of total EU electricity production) SE, 7.3% UK, 7.9% SP, 5.8% BE,4.8% CZ, 2.5% GE, 16.3% FI, 2.4% BU, 1.8% Other 12.4% SK, 1.7% HU, 1.4% LT, 1.1% FR, 45.5% SI, 0.6% NL, RO, 0.5% 0.4% Source PRIS 14. 9. 2010 5 Central & Eastern Europe - Nuclear Landscape Russia Lithuania Ukraine 6 VVER440 Poland 1 RBMK 1300 2 VVER440 8 VVER1000 Min. of Energy 13 VVER1000 NNEGC State owned 11 RBMK 1 BN600 4 Graph Mod BWR Czech Republic Rosenergoatom State 4 VVER440 owned 2 VVER1000 CEZ/ 67% State Romania owned 2 Candu PHW Nuclearelectrica State owned Slovak Republic 4/6 VVER440 Bulgaria ENEL 67% owned 2/4 VVER1000 NEC State owned Hungary Armenia 4 VVER 440 1 VVER440 MVM State owned Armatomenergo, State owned 14.
    [Show full text]
  • Vver and Rbmk Cross Section Libraries for Origen-Arp
    VVER AND RBMK CROSS SECTION LIBRARIES FOR ORIGEN-ARP Germina Ilas, Brian D. Murphy, and Ian C. Gauld, Oak Ridge National Laboratory, USA Introduction An accurate treatment of neutron transport and depletion in modern fuel assemblies characterized by heterogeneous, complex designs, such as the VVER or RBMK assembly configurations, requires the use of advanced computational tools capable of simulating multi-dimensional geometries. The depletion module TRITON [1], which is part of the SCALE code system [2] that was developed and is maintained at the Oak Ridge National Laboratory (ORNL), allows the depletion simulation of two- or three-dimensional assembly configurations and the generation of burnup-dependent cross section libraries. These libraries can be saved for subsequent use with the ORIGEN-ARP module in SCALE. This later module is a faster alternative to TRITON for fuel depletion, decay, and source term analyses at an accuracy level comparable to that of a direct TRITON simulation. This paper summarizes the methodology used to generate cross section libraries for VVER and RBMK assembly configurations that can be employed in ORIGEN-ARP depletion and decay simulations. It briefly describes the computational tools and provides details of the steps involved. Results of validation studies for some of the libraries, which were performed using isotopic assay measurement data for spent fuel, are provided and discussed. Cross section libraries for ORIGEN-ARP Methodology The TRITON capability to perform depletion simulations for two-dimensional (2-D) configurations was implemented by coupling of the 2-D transport code NEWT with the point depletion and decay code ORIGEN-S. NEWT solves the transport equation on a 2-D arbitrary geometry grid by using an SN approach, with a treatment of the spatial variable that is based on an extended step characteristic method [3].
    [Show full text]
  • Passive Safety Injection System Design and Simulation for Small Scale Pressurized Water Reactor
    Passive Safety Injection System Design and Simulation for Small Scale Pressurized Water Reactor Muhammad Tahir A dissertation submitted for the degree of “Doctor of Philosophy” (PhD) in Pakistan Institute of Engineering and Applied Sciences Islamabad Pakistan May 2011 Declaration I declare that all material in this thesis which is not my own work has been identified and that no material has previously been submitted and approved for the award of a degree in this or in any other university. Signature: __________________________ Author’s Name: (Muhammad Tahir) Supervisor Dr. Imran Rafiq Chughtai Principal Engineer Department of Chemical and Materials Engineering Pakistan Institute of Engineering and Applied Sciences [PIEAS] Islamabad, Pakistan. Head, DNE, PIEAS 2 Acknowledgements All praises and thanks to God, the most Merciful, Compassionate, Gracious and Beneficent who has created man and is a source of knowledge and wisdom. At the very outset, I am thankful to my supervisors, Dr. Imran Rafiq Chughtai, PE and Dr. Muhammad Aslam, CE for their supervision, technical advices throughout the investigations and preparation of this manuscript. I am greatly indebted to director Imtiaz Rabbani for his administrative guidance. I am also grateful to my professors at PIEAS especially Dr. Muhammad Aslam, Dr. Tehsin Hamid, Dr. Naseem Irfan, Dr. Mansoor Hamid Inayat, Dr. Nasir Majid Mirza, Dr. Sikandar Majid Mirza and Dr. Muhammad Tufail. I am thankful to Dr. Muhammad Arfin Khan for his assistance in visiting Texas Tech University USA and guidance in educational and research activities. I am also grateful to my friends and colleagues who ensured a creative and good working environment and helped me in technical and non-technical matters.
    [Show full text]
  • Fast-Spectrum Reactors Technology Assessment
    Clean Power Quadrennial Technology Review 2015 Chapter 4: Advancing Clean Electric Power Technologies Technology Assessments Advanced Plant Technologies Biopower Clean Power Carbon Dioxide Capture and Storage Value- Added Options Carbon Dioxide Capture for Natural Gas and Industrial Applications Carbon Dioxide Capture Technologies Carbon Dioxide Storage Technologies Crosscutting Technologies in Carbon Dioxide Capture and Storage Fast-spectrum Reactors Geothermal Power High Temperature Reactors Hybrid Nuclear-Renewable Energy Systems Hydropower Light Water Reactors Marine and Hydrokinetic Power Nuclear Fuel Cycles Solar Power Stationary Fuel Cells U.S. DEPARTMENT OF Supercritical Carbon Dioxide Brayton Cycle ENERGY Wind Power Clean Power Quadrennial Technology Review 2015 Fast-spectrum Reactors Chapter 4: Technology Assessments Background and Current Status From the initial conception of nuclear energy, it was recognized that full realization of the energy content of uranium would require the development of fast reactors with associated nuclear fuel cycles.1 Thus, fast reactor technology was a key focus in early nuclear programs in the United States and abroad, with the first usable nuclear electricity generated by a fast reactor—Experimental Breeder Reactor I (EBR-I)—in 1951. Test and/or demonstration reactors were built and operated in the United States, France, Japan, United Kingdom, Russia, India, Germany, and China—totaling about 20 reactors with 400 operating years to date. These previous reactors and current projects are summarized in Table 4.H.1.2 Currently operating test reactors include BOR-60 (Russia), Fast Breeder Test Reactor (FBTR) (India), and China Experimental Fast Reactor (CEFR) (China). The Russian BN-600 demonstration reactor has been operating as a power reactor since 1980.
    [Show full text]